ML20236A175
| ML20236A175 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/07/1989 |
| From: | Murphy M, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236A172 | List: |
| References | |
| 50-285-89-12, NUDOCS 8903160438 | |
| Download: ML20236A175 (4) | |
See also: IR 05000285/1989012
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APPENDIX
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report: 50-285/89-12
Operating License: DPR-40
Docket:
50-285
Licensee: Omaha Public Power District (OPPD)
1623 Harney Street
Omaha, Nebraska 68102
Facility Name: Fort Calhoun Station (FCS)
Inspection At:
Inspection Conducted:
February 21-24, 1989
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Inspector:
M. E. Purpt[y', Reactor In!ipector Test Programs
Date
Section Division of Reactor Safety
3/7/#f
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Approved:
W. C. Seidle/ Chief, Test Programs Section
Date
Division of Reactor Safety
Inspection Summary
Inspection Conducted February 21-24, 1989 (Report 50-285/89-121
Areas Inspected:
Routine, unannounced inspection of post modification testing
and followup on the main steam safety valve issue.
Results: Within the areas inspected, no violations or deviations were
identified. The licensee's post modification testing was found to be in
conformance with the detailed design requirements. The testing acceptance
criteria were satisfactory and in conformance with Technical
Specifications (TS), regulatory requirements, and industry codes and standards.
The licensee has not identified the root cause of the three main steam safety
valves that failed to open during the last surveillance test (ST).
The
licensee does plan to modify or change the test method for the next ST.
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DETAILS
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1.
Persons Contacted
- C, Brunnert, Supervisor, Operations Quality Assurance (QA) .
- H. Faulhaber, Manager, Electrical Instrumentation and Control (180)
- J. Gasper Training Manager
- R. Jaworski, Manager, Station Engineering
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J.*Kecy, Supervisor, System Engineering
- L..Kusek, Acting Plant Menager
- D. Matthews,-Acting Supervisor, Station Licensing
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- R. Phelps, Manager, Design Engineering
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B. Stecker, Test Engineer
NRC
P. Harrell, Senior Resident inspector
- T. Reis, Resident Inspector
The NRC inspector also interviewed other licensee employees during the
inspection.
- Denotes those attending the exit interview on February 24, 1989.
'2.
Modification Testing
(72701)
.The inspection was conducted to ascertain that the licensee's modification
testing program for new or modified structures, systems, and components
was in conformance with detailed design documents, regulatory requirements,
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TS,'and industry codes and standards. The NRC inspector reviewed completed
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Modifications 81-51, " Control Room Ventilation System Modification;" and
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'81-064, " Reactor Coolant System Hot Leg Level Indication Modification."
- Modification 81-51 increased the capacity of the control room air
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conditioning units so that only one unit is needed for operation. This
modification also eliminated unfiltered air leakage into the control room
and significantly reduced ambient heat gains to the system.
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Modification 81-064 was installed to prevent reaching a reactor coolant
system level below that required for adequate suction head for the low
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pressure safety injection pumps during any shutdown and drained down
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condition. This modification replaced the present level indicator with a
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dual indicator. A "RCS Refueling Level Low" alarm was installed.
The review of these completed modifications determined that test
requirements were properly identified for component and system
construction phase testing. Wiring continuity and separation checks,
calibration of instrumentation and setpoints, and component functional
tests were satisfactorily accomplished.
The acceptance tests were conducted using procedures which contained the
appropriate features of scope, precautions, references, prerequisites,
acceptance criteria, tagouts, and system lineups. The procedures and
procedure change notices were reviewed and approved in accordance with the
licensee's administrative procedures. The licensee's review and
evaluation of the completed test procedures satisfactorily addressed that
the test results met the established acceptance criteria.
Test problems
were resolved and retesting accomplished where required.
No violations or deviations were identified in this area of the
inspection.
3.
Main Steam Safety Valves (MSSV) Setpoint Problem (92700)
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The NRC inspector reviewed Licensee Event Report (LER)88-023, which
reported the MSSV setpoint problem encountered during the last refueling
outage. While performing Surveillance Test (ST) ST-MSSV-1, " Main Steam
Safety Valve Test," four of the MSSVs failed their lift point test. One
valve was satisfactorily reset and retested.
Three of the valvos failed to lift even with maximum allowed test pressure
applied. These valves are Dresser Industries Maxiflow Model 6-inch
1500 psig class relief valves.
The licensee obtained concurrence from the vendor, issued a procedure
change, and manually cycled all three valves. The original ST was
repeated and all three valves again failed to lift with maximum allowed
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test pressure applied. The licensee uses the Hydrostet method for relief
valve testing with the system at normal operating temperature and
pressure.
Subsequent to the second test attempt, the three valves were removed from
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the system and sent to Wyle Laboratories. The laboratory was able to lift
all three valves, two were marginally out-of-specification high and one
was found to be in specification. All three valves were subsequently
found to exceed the post-lift seat leakage test and were refurbished by a
Dresser representative.
A review of previously reported MSSV setpoint problems reported in
LERs82-020, 84-002,85-006, and 87-003 did not reveal any pattern of
events.
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A review of the test reported in LER 88-023 did not reveal any sequence of
. events or personnel actions that would explain or provide leads to a
solution of the failure of the three valves to lift in situ. The licensee
is still attempting to determine the root cause and at this time is
studying the alternate test methods available to be used during the next
refueling outage.
No violations or deviations were identified in this area of the
inspection.
4
Exit Interview
The NRC inspector met with the personnel denoted in paragraph 1 on
February 24, 1989. The NRC inspector summarized the scope and findings of
the inspection. The licensee did not identify, as proprietary, any of the
infomation provided to, or reviewed by, the NRC inspector.